CN117637197A - System for discharging pressure released to high altitude under serious accident of ocean floating nuclear power platform - Google Patents
System for discharging pressure released to high altitude under serious accident of ocean floating nuclear power platform Download PDFInfo
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- CN117637197A CN117637197A CN202311555955.9A CN202311555955A CN117637197A CN 117637197 A CN117637197 A CN 117637197A CN 202311555955 A CN202311555955 A CN 202311555955A CN 117637197 A CN117637197 A CN 117637197A
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- 238000007599 discharging Methods 0.000 title claims abstract description 71
- 238000007667 floating Methods 0.000 title claims abstract description 59
- 230000002285 radioactive effect Effects 0.000 claims abstract description 51
- 238000001914 filtration Methods 0.000 claims abstract description 39
- 239000000779 smoke Substances 0.000 claims abstract description 16
- 238000012806 monitoring device Methods 0.000 claims description 25
- 238000004891 communication Methods 0.000 claims description 17
- 238000002955 isolation Methods 0.000 claims description 13
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 13
- 238000001514 detection method Methods 0.000 claims description 12
- 239000002184 metal Substances 0.000 claims description 12
- 239000000835 fiber Substances 0.000 claims description 8
- 238000005406 washing Methods 0.000 claims description 5
- 238000012545 processing Methods 0.000 claims description 4
- 238000007789 sealing Methods 0.000 claims description 3
- 238000013022 venting Methods 0.000 claims 7
- 230000005855 radiation Effects 0.000 abstract description 15
- 230000007613 environmental effect Effects 0.000 abstract description 3
- 239000007789 gas Substances 0.000 description 41
- 238000000034 method Methods 0.000 description 10
- 230000008569 process Effects 0.000 description 10
- 238000012544 monitoring process Methods 0.000 description 7
- 239000000443 aerosol Substances 0.000 description 6
- 239000000700 radioactive tracer Substances 0.000 description 6
- 239000002245 particle Substances 0.000 description 5
- 238000011156 evaluation Methods 0.000 description 4
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 3
- 238000007664 blowing Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 229910052740 iodine Inorganic materials 0.000 description 3
- 239000011630 iodine Substances 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000007865 diluting Methods 0.000 description 2
- 230000002349 favourable effect Effects 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 230000004044 response Effects 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 108010066114 cabin-2 Proteins 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000006837 decompression Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010790 dilution Methods 0.000 description 1
- 239000012895 dilution Substances 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000004927 fusion Effects 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
Classifications
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention relates to the technical field of nuclear safety and radiation protection of a floating nuclear power platform, and discloses a system for releasing pressure and discharging to the high altitude under serious accidents of the ocean floating nuclear power platform. Aiming at the risk of overpressure of the containment vessel of the reactor after a serious accident is placed on the ocean floating nuclear power platform, the pressure relief emission scheme combining filtering and high-altitude emission is provided for carrying out pressure relief emission on radioactive high-temperature and high-pressure steam in the containment vessel by combining the resource conditions on the ship and the environmental characteristics. In addition, a trace smoke generating device is added in the high-altitude discharge device, and the direction of radioactive gas discharge of related personnel is reminded through trace smoke, so that the influence of radioactive gas discharge on personnel radiation safety is reduced. Based on the measures, the integrity of the containment of the reactor cabin is guaranteed, a large amount of radioactivity in the containment of the reactor cabin is released uncontrollably to the environment after serious accidents, and meanwhile, the radioactive influence of radioactive emission on workers of the floating nuclear power platform is reduced by adjusting the posture of the floating nuclear power platform.
Description
Technical Field
The invention relates to the technical field of nuclear safety and radiation protection of nuclear power devices of floating nuclear power platforms, in particular to a system for discharging pressure released to the high altitude under serious accidents of ocean floating nuclear power platforms.
Background
The ocean floating nuclear power platform is used as a nuclear facility for offshore movement, is a power source for propulsion and power supply of the floating nuclear power platform, has frequent change of system operation working conditions, is limited by resource conditions such as space, weight and the like on a ship, and is simplified and optimized in the design of capacity and redundancy of a safety facility. Thus, the probability and risk of accident for a marine floating nuclear power platform is relatively high, and the safety risk of transition to a serious accident after design basis accident is relatively high, relative to land nuclear facilities. Once serious accidents occur on the ocean floating nuclear power platform, serious consequences such as fuel element damage, reactor core fusion, hydrogen explosion, stack cabin containment vessel overpressure and the like can be caused.
The reactor containment is an important barrier for radioactive containment of the ocean floating nuclear power platform after an accident, and corresponding measures must be taken to ensure the integrity of the reactor containment. The pressure bearing of the reactor containment is low and the internal free volume is small due to the limitation of the resource conditions such as space and weight on the ship, and in order to ensure the structural integrity of the reactor containment after serious accidents, an outward pressure relief and discharge system of the reactor containment is required to be arranged and is used for rapidly discharging radioactive steam in the reactor containment after serious accidents, so that the pressure of the reactor containment does not exceed a limit value; meanwhile, in the process of outwards releasing pressure and discharging, radioactive substances are removed in a filtering mode and the like, so that the influence of discharging on personnel and environment on a ship is reduced, and the radiation safety in the discharging process is ensured.
At present, the land nuclear power station comprehensively considers the relief measures of serious accidents, and a passive containment heat conduction system, a containment filtering and discharging system and the like are generally arranged to maintain the integrity of the containment. For the ocean floating nuclear power platform, space and weight resources on the ship are limited, a high-power passive containment cooling system of a land-based nuclear power station cannot be directly used, and large-scale filtering and discharging devices such as a sand bed filter and a metal fiber filter are difficult to remove radioactive substances. Therefore, the technical requirement for guaranteeing the integrity of the containment of the ship cabin after serious accidents of the ocean floating nuclear power platform is high, the difficulty is high, a reasonable outward pressure relief emission and radioactivity removal emission scheme is arranged, and the radiation safety of on-board workers and the environment is guaranteed while the integrity of the containment of the ship cabin is guaranteed.
Disclosure of Invention
Aiming at the defects in the prior art, the system for releasing pressure to the high altitude under serious accident of the ocean floating nuclear power platform is provided, and is used for quickly releasing radioactive steam in the containment of the reactor after serious accident, so that the pressure of the containment of the reactor does not exceed the limit value, and meanwhile, in the process of releasing pressure to the outside, the influence of the emission on personnel and the environment on a ship is required to be reduced, and the radiation safety in the process of emission is ensured.
The technical scheme adopted by the invention for solving the technical problems is as follows:
system for releasing pressure to high altitude under serious accident of ocean floating nuclear power platform, which is characterized in that: the filter comprises a stack cabin safety shell, an auxiliary cabin, a filter discharge device and a high-altitude discharge device, wherein the stack cabin safety shell is adjacent to the auxiliary cabin; a communication pipeline is arranged between the auxiliary cabin and the safety shell of the cabin, the outer wall of the communication pipeline is fixedly connected with the cabin wall in a sealing way, the inner side end of the communication pipeline is communicated with the inner space of the safety shell of the cabin, the outer side end of the communication pipeline is communicated with the inlet of the filter discharge device arranged in the auxiliary cabin, and electric safety isolation valves are arranged at both ends of the communication pipeline and both ends of the filter discharge device; the high-altitude discharge device is arranged at the high point of a mast or a chimney of the floating nuclear power platform, and a trace smoke generating device is arranged in the high-pressure discharge device; the filter discharge device is connected with the high-altitude discharge device through a pipeline, the pipeline penetrates through the multi-layer cabin, and an electric stop valve and an electric stop check valve are sequentially arranged on the pipeline between the filter discharge device and the high-altitude discharge device along the medium flowing direction; the attitude of the floating nuclear power platform is adjusted according to meteorological conditions, so that the longitudinal direction of the floating nuclear power platform is vertical to the wind direction, and radioactive gas is blown away from the ship body.
According to the technical scheme, the filtering and discharging device adopts a mode of combining a Venturi water washer and metal fibers for filtering.
According to the technical scheme, the filtering and discharging device comprises a shell serving as a pressure container, wherein a mixed gas inlet pipeline, a Venturi water washing filter, a steam-water separator, a metal filter screen and a mixed gas outlet pipeline are sequentially arranged in the shell along the flowing direction of the mixed gas.
According to the technical scheme, the emergency discharging device also comprises an emergency discharging branch, the emergency discharging branch is connected with the filtering discharging device in parallel, and an electric safety isolating valve is arranged on the emergency discharging branch; the emergency discharge branch is connected between the communicating pipe and the high-altitude discharge device.
According to the technical scheme, the inlet end of the emergency discharge branch is connected between the electric safety isolation valve outside the communicating pipeline and the electric safety isolation valve at the inlet end of the filtering and discharging device, and the outlet end of the emergency discharge branch is connected between the electric safety isolation valve at the outlet end of the filtering and discharging device and the electric stop valve.
According to the technical scheme, the pipeline between the filtering and discharging device and the high-altitude discharging device is provided with the outside-pipe radioactivity on-line monitoring device, and the outside-pipe radioactivity on-line monitoring device is connected with the trace smoke generating device in the high-pressure discharging device.
According to the technical scheme, the on-line monitoring device for the radioactivity outside the pipe comprises a detection device, a local shielding shell and corresponding data processing equipment, wherein the detection device is attached to a pipeline between the filtering and discharging device and the high-altitude discharging device, and the local shielding shell covers the detection device and the corresponding pipeline.
According to the technical scheme, the on-line monitoring device for radioactivity outside the pipe is positioned between the electric stop valve and the filtering and discharging device.
According to the technical scheme, in the pressure relief discharging device comprising the emergency discharging branch, the outside-pipe radioactivity on-line monitoring device is positioned between the outlet of the emergency discharging branch and the electric stop valve.
The invention has the following beneficial effects:
1. aiming at the risk of overpressure of the containment vessel of the reactor after a serious accident is placed on the ocean floating nuclear power platform, the pressure relief emission scheme combining filtering and high-altitude emission is provided for carrying out pressure relief emission on radioactive high-temperature and high-pressure steam in the containment vessel by combining the resource conditions on the ship and the environmental characteristics. In addition, a trace smoke generating device is added in the high-altitude discharge device, and the direction of radioactive gas discharge of related personnel is reminded through trace smoke, so that the influence of radioactive gas discharge on personnel radiation safety is reduced. Based on the measures, the integrity of the containment of the reactor cabin is guaranteed, a large amount of radioactivity in the containment of the reactor cabin is released uncontrollably to the environment after serious accidents, and meanwhile, the radioactive influence of radioactive emission on workers of the floating nuclear power platform is reduced by adjusting the posture of the floating nuclear power platform.
2. The venturi water scrubber is used for removing most radioactive aerosol particles and radioactive iodine, condensing the discharged gas, and the metal fiber filter is used for removing radioactive aerosol particles with smaller particle size. The overhead discharge device dilutes the radioactive exhaust gas and adds a visible tracer gas according to the measurement results of radioactivity and temperature, so that related personnel know that the radioactive exhaust gas is being discharged and the influence of radioactive emission on the radiation safety of the radioactive exhaust gas is reduced. And adjusting the posture of the floating nuclear power platform according to meteorological conditions, so that the floating nuclear power platform is vertical to the wind direction and is favorable for blowing away the ship body with radioactive gas, diluting the mixed gas to be discharged after the posture is adjusted, adding visible tracer smoke, and arranging discharge ports at equal-altitude points of a mast or a chimney of the floating nuclear power platform for discharge. In the process of outwards discharging the high-temperature and high-pressure mixed gas, according to the time of opening the discharge, a management and control measure is adopted for the periphery of the discharge pipeline, so that the radioactive influence on the staff of the floating nuclear power platform in the discharge process is reduced.
3. The radioactivity of the outward discharged mixed gas is monitored on line in an on-line monitoring mode, and data support is provided for carrying out radioactive emission result evaluation, radiation protection measures and the like. The on-line monitoring device for the radioactivity outside the tube is arranged, the on-line monitoring device for the radioactivity outside the tube is partially shielded, the complexity of a monitoring system is reduced, the influence of the background on the monitoring result is reduced, and the reliability of the monitoring device is improved.
Drawings
FIG. 1 is a schematic diagram of a construction of an embodiment of the present invention;
FIG. 2 is a schematic diagram of an on-line monitoring device for radioactivity outside a tube according to an embodiment of the present invention;
FIG. 3 is a schematic view of the structure of a filter drain device according to an embodiment of the present invention;
in the figure, 1, a stack cabin safety shell; 2. an auxiliary cabin; 3. a filter discharge device; 3-1, a shell; 3-2, a mixed gas inlet pipeline; 3-3, venturi water washing filter; 3-4, a steam-water separator; 3-5, a metal filter screen; 3-6, a mixed gas outlet pipeline; 4. a high-altitude discharge device; 5. a communication pipe; 6. an electric safety isolation valve; 7. masts or chimneys; 8. an electric shut-off valve; 9. an electric shut-off check valve; 10. an emergency discharge branch; 11. an out-of-tube radioactivity on-line monitoring device; 11-1, a detection device; 11-2, partial shielding shell.
Detailed Description
The invention will now be described in detail with reference to the drawings and examples.
Referring to fig. 1 to 3, the ocean floating nuclear power platform provided by the invention is provided with a system for releasing pressure to the high altitude in case of serious accidents.
Example 1
The device comprises a stacking cabin safety shell 1, an auxiliary cabin 2, a filtering and discharging device 3 and a high-altitude discharging device 4, wherein the stacking cabin safety shell is adjacent to the auxiliary cabin; a communication pipeline 5 is arranged between the auxiliary cabin and the safety shell of the cabin, the outer wall of the communication pipeline is fixedly connected with the cabin wall in a sealing way, the inner side end of the communication pipeline is communicated with the inner space of the safety shell of the cabin, the outer side end of the communication pipeline is communicated with the inlet of the filter discharge device arranged in the auxiliary cabin, and electric safety isolation valves 6 are arranged at both ends of the communication pipeline and both ends of the filter discharge device; the high-altitude discharge device is arranged at the high point of the mast or the chimney 7 of the floating nuclear power platform, and a trace smoke generating device is arranged in the high-pressure discharge device; the filtering and discharging device is connected with the high-altitude discharging device through a pipeline, the pipeline penetrates through the multi-layer cabin, and an electric stop valve 8 and an electric stop check valve 9 are sequentially arranged on the pipeline between the filtering and discharging device and the high-altitude discharging device along the medium flowing direction; the attitude of the floating nuclear power platform is adjusted according to meteorological conditions, so that the longitudinal direction of the floating nuclear power platform is vertical to the wind direction, and radioactive gas is blown away from the ship body.
In the embodiment, aiming at the risk of overpressure of the containment vessel of the reactor after a serious accident is placed on the ocean floating nuclear power platform, the pressure relief emission scheme combining filtration and high-altitude emission is provided for carrying out pressure relief emission on radioactive high-temperature high-pressure steam in the containment vessel by combining the resource conditions of the ship and the environmental characteristics of the ship. In addition, a trace smoke generating device is added in the high-altitude discharge device, and the direction of radioactive gas discharge of related personnel is reminded through trace smoke, so that the influence of radioactive gas discharge on personnel radiation safety is reduced. Based on the measures, the integrity of the containment of the reactor cabin is guaranteed, a large amount of radioactivity in the containment of the reactor cabin is released uncontrollably to the environment after serious accidents, and meanwhile, the radioactive influence of radioactive emission on workers of the floating nuclear power platform is reduced by adjusting the posture of the floating nuclear power platform.
Example 2
The structure and principle of embodiment 2 are similar to those of embodiment 1, except that: the filtering and discharging device adopts a mode of combining a Venturi water washer and metal fibers for filtering.
Specifically, the filtering and discharging device comprises a shell 3-1 serving as a pressure vessel, wherein a mixed gas inlet pipeline 3-2, a venturi water washing filter 3-3, a steam-water separator 3-4, a metal filter screen 3-5 and a mixed gas outlet pipeline 3-6 are sequentially arranged in the shell along the flowing direction of the mixed gas. The filtering and discharging device adopts an integrated design idea, integrates a Venturi water-washing filter and a metal fiber filter in a shell serving as a pressure container, and simultaneously sets a steam-water separator to reduce the humidity of mixed gas entering the metal fiber filter, so that the filtering efficiency of radioactive aerosol and iodine is improved while the volume and the weight of the device are reduced.
In this embodiment, a venturi scrubber is used to remove the vast majority of radioactive aerosol particles and radioactive iodine while condensing the exhaust gases, and a metal fiber filter is used to remove the smaller size radioactive aerosol particles. The overhead discharge device dilutes the radioactive exhaust gas and adds a visible tracer gas according to the measurement results of radioactivity and temperature, so that related personnel know that the radioactive exhaust gas is being discharged and the influence of radioactive emission on the radiation safety of the radioactive exhaust gas is reduced. And adjusting the posture of the floating nuclear power platform according to meteorological conditions, so that the floating nuclear power platform is vertical to the wind direction and is favorable for blowing away the ship body with radioactive gas, diluting the mixed gas to be discharged after the posture is adjusted, adding visible tracer smoke, and arranging discharge ports at equal-altitude points of a mast or a chimney of the floating nuclear power platform for discharge. In the process of outwards discharging the high-temperature and high-pressure mixed gas, according to the time of opening the discharge, a management and control measure is adopted for the periphery of the discharge pipeline, so that the radioactive influence on the staff of the floating nuclear power platform in the discharge process is reduced.
Example 3
Embodiment 3 differs from embodiment 1 in that when the structure and principle are close to those of embodiment 1, it is that: the emergency discharging branch circuit 10 is connected with the filtering discharging device in parallel, and an electric safety isolating valve is arranged on the emergency discharging branch circuit; the emergency discharge branch is connected between the communicating pipe and the high-altitude discharge device. When the filtering and discharging device can not timely treat the radioactive high-pressure mixed gas and then discharge the radioactive high-pressure mixed gas to the sea, the emergency discharging branch is opened.
In embodiment 3, preferably, the inlet end of the emergency discharge branch is connected between the electric safety isolation valve outside the communication pipe and the electric safety isolation valve at the inlet end of the filter discharge device, and the outlet end of the emergency discharge branch is connected between the electric safety isolation valve at the outlet end of the filter discharge device and the electric stop valve.
Example 4
Embodiment 4 differs from embodiments 1-3 in the structure and principle when it is close to those of embodiments in that: in order to acquire the outwards discharged radioactive data, carry out the result evaluation of the radioactive emergency discharge, provide important support for the personnel on the floating nuclear power platform to carry out radiation protection measures and relevant emergency response, and a pipeline between the filtering discharge device and the high-altitude discharge device is provided with an out-of-pipe radioactivity on-line monitoring device 11. In the embodiment in the figure, an outside-tube radioactivity on-line monitoring device is connected with a tracer smoke generating device in a high-pressure discharge device, and when radioactive medium flowing is detected, the tracer smoke generating device is started.
The on-line monitoring device for radioactivity outside the pipe comprises a detection device 11-1, a local shielding shell 11-2 and corresponding data processing equipment, wherein the detection device is attached to a pipeline between the filtering and discharging device and the high-altitude discharging device, and the local shielding shell covers the detection device and the corresponding pipeline. In this embodiment, the materials of the detection device, the partial shielding shell and the corresponding data processing equipment are all selected from the existing equipment or materials. The radioactivity of the outward discharged mixed gas is monitored on line in an on-line monitoring mode, and data support is provided for carrying out radioactive emission result evaluation, radiation protection measures and the like. The on-line monitoring device for the radioactivity outside the tube is arranged, the on-line monitoring device for the radioactivity outside the tube is partially shielded, the complexity of a monitoring system is reduced, the influence of the background on the monitoring result is reduced, and the reliability of the monitoring device is improved.
Specifically, the outside-tube radioactivity on-line monitoring device is positioned between the electric stop valve and the filtering and discharging device. In addition, in the pressure release discharging device comprising the emergency discharging branch, the outside-pipe radioactivity on-line monitoring device is positioned between the outlet of the emergency discharging branch and the electric stop valve, so that the detection of relevant data of medium discharged into the high altitude in emergency is facilitated.
In the process of outwards discharging the high-temperature and high-pressure mixed gas, a management and control measure is adopted for the periphery of the discharge pipeline, so that the radioactive influence on the staff of the ocean floating nuclear power platform in the discharge process is reduced.
The working principle of the invention is as follows:
through setting up small-size integrated filtration discharging equipment, carry out the decompression to the mixed steam of taking radioactivity, filter radioactive iodine and aerosol simultaneously, reduce the influence to floating nuclear power platform and environment, reduced the demand of system to total resource simultaneously. According to the attitude of the floating nuclear power platform, the floating nuclear power platform is vertical to the wind direction and is beneficial to blowing away the radioactive gas from the ship body, after the attitude is adjusted, the mixed gas treated by the filtering and discharging device is diluted and the visible trace smoke is added, the high-altitude discharging device is arranged at the equal-altitude point of the mast or the chimney of the floating nuclear power platform for discharging, so that related personnel know that the radioactive waste gas is being discharged, and the influence of the radioactive discharging on the radiation safety of the floating nuclear power platform is reduced.
In addition, the radioactivity of the externally discharged mixed gas is monitored on line in an on-line monitoring mode, and an on-line monitoring device for the radioactivity outside the pipe is arranged. The outside-pipe radioactivity online monitoring device is utilized to acquire outwards discharged radioactivity data, the dilution times required by the high-altitude discharging device, the quantity of added visible trace gas and other parameters are acquired, the result evaluation of radioactivity emergency discharging is carried out, and important support is provided for carrying out radiation protection measures and relevant emergency response on workers on the floating nuclear power platform.
The foregoing is merely illustrative of the present invention and is not intended to limit the scope of the invention, which is defined by the claims and their equivalents.
Claims (9)
1. System for releasing pressure to high altitude under serious accident of ocean floating nuclear power platform, which is characterized in that: the filter comprises a stack cabin safety shell, an auxiliary cabin, a filter discharge device and a high-altitude discharge device, wherein the stack cabin safety shell is adjacent to the auxiliary cabin; a communication pipeline is arranged between the auxiliary cabin and the safety shell of the cabin, the outer wall of the communication pipeline is fixedly connected with the cabin wall in a sealing way, the inner side end of the communication pipeline is communicated with the inner space of the safety shell of the cabin, the outer side end of the communication pipeline is communicated with the inlet of the filter discharge device arranged in the auxiliary cabin, and electric safety isolation valves are arranged at both ends of the communication pipeline and both ends of the filter discharge device; the high-altitude discharge device is arranged at the high point of a mast or a chimney of the floating nuclear power platform, and a trace smoke generating device is arranged in the high-pressure discharge device; the filter discharge device is connected with the high-altitude discharge device through a pipeline, the pipeline penetrates through the multi-layer cabin, and an electric stop valve and an electric stop check valve are sequentially arranged on the pipeline between the filter discharge device and the high-altitude discharge device along the medium flowing direction; the attitude of the floating nuclear power platform is adjusted according to meteorological conditions, so that the longitudinal direction of the floating nuclear power platform is vertical to the wind direction, and radioactive gas is blown away from the ship body.
2. The marine floating nuclear power platform severe accident aloft venting system of claim 1, wherein: the filtering and discharging device adopts a mode of combining a Venturi water washer and metal fibers for filtering.
3. The marine floating nuclear power platform severe accident aloft venting system of claim 2, wherein: the filtering and discharging device comprises a shell serving as a pressure container, and a mixed gas inlet pipeline, a Venturi water washing filter, a steam-water separator, a metal filter screen and a mixed gas outlet pipeline are sequentially arranged in the shell along the flowing direction of the mixed gas.
4. The marine floating nuclear power platform severe accident aloft venting system of claim 1, wherein: the emergency discharging branch is connected with the filtering discharging device in parallel, and an electric safety isolating valve is arranged on the emergency discharging branch; the emergency discharge branch is connected between the communicating pipe and the high-altitude discharge device.
5. The marine floating nuclear power platform severe accident aloft venting system of claim 4, wherein: the inlet end of the emergency discharge branch is connected between the electric safety isolation valve outside the communicating pipeline and the electric safety isolation valve at the inlet end of the filtering and discharging device, and the outlet end of the emergency discharge branch is connected between the electric safety isolation valve at the outlet end of the filtering and discharging device and the electric stop valve.
6. The marine floating nuclear power platform severe accident situation overhead pressure relief discharge system according to any one of claims 1-5, wherein: an out-of-tube radioactivity on-line monitoring device is arranged on a pipeline between the filtering and discharging device and the high-altitude discharging device, and the out-of-tube radioactivity on-line monitoring device is connected with a trace smoke generating device in the high-pressure discharging device.
7. The marine floating nuclear power platform severe accident aloft venting system of claim 6, wherein: the on-line monitoring device for the radioactivity outside the pipe comprises a detection device, a local shielding shell and corresponding data processing equipment, wherein the detection device is attached to a pipeline between the filtering and discharging device and the high-altitude discharging device, and the local shielding shell covers the detection device and the corresponding pipeline.
8. The marine floating nuclear power platform severe accident aloft venting system of claim 6, wherein: the on-line monitoring device for radioactivity outside the tube is positioned between the electric stop valve and the filtering and discharging device.
9. The marine floating nuclear power platform severe accident aloft venting system of claim 6, wherein: in the pressure relief discharge device comprising the emergency discharge branch, the out-of-pipe radioactivity on-line monitoring device is positioned between the outlet of the emergency discharge branch and the electric stop valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311555955.9A CN117637197A (en) | 2023-11-17 | 2023-11-17 | System for discharging pressure released to high altitude under serious accident of ocean floating nuclear power platform |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311555955.9A CN117637197A (en) | 2023-11-17 | 2023-11-17 | System for discharging pressure released to high altitude under serious accident of ocean floating nuclear power platform |
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| Publication Number | Publication Date |
|---|---|
| CN117637197A true CN117637197A (en) | 2024-03-01 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202311555955.9A Pending CN117637197A (en) | 2023-11-17 | 2023-11-17 | System for discharging pressure released to high altitude under serious accident of ocean floating nuclear power platform |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117637197A (en) |
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2023
- 2023-11-17 CN CN202311555955.9A patent/CN117637197A/en active Pending
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